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The effects of surface area to solution volume on waste glass leaching

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:5462811
Silicon solubility limitations appear to control the rate of corrosion of a complex simulated nuclear waste glass at relatively high values of the glass surface area to solution volume ratio (SA/V). Undersaturated glass components such as sodium and boron were affected by SA/V in a manner similar to silicon. Under relatively low SA/V conditions, glass corrosion was unaffected by changes in the SA/V ratio. Congruent dissolution was never observed, in contrast to previous results for simple and certain complex silicate glasses. Increases in the SA/V value may be a viable method for performing accelerated leach resistance testing of nuclear waste forms.
Research Organization:
Pacific Northwest Laboratory, P.O. Box 999, Richland, Washington 99352
DOE Contract Number:
AC06-76RL01830
OSTI ID:
5462811
Journal Information:
Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 62:2; ISSN NUTYB
Country of Publication:
United States
Language:
English